Multi-machine transport analysis of hybrid discharges from the ITPA profile database
Imbeaux, F; Artaud, J F; Kinsey, J; Tala, T J J; Bourdelle, C; Fujita, T; Greenfield, C; Joffrin, E; Na, Y S; Parail, V V; Sakamoto, Y; Sips, A C C; Voitsekovitch, I; Imbeaux, F; Association EURATOM-CEA, CEA/DSM/DRFC, CEA Cadarache, France; Artaud, J F; Association EURATOM-CEA, CEA/DSM/DRFC, CEA Cadarache, France; Kinsey, J; Lehigh University, Bethlehem, PA 18015, USA; Tala, T J J; Association EURATOM-Tekes, VTT Process, Finland; Bourdelle, C; Association EURATOM-CEA, CEA/DSM/DRFC, CEA Cadarache, France; Fujita, T; Naka Fusion Research Establishment, Japan Atomic Energy Research Institute, Naka-machi, Naka-gun, Ibaraki-ken 311-0193, Japan; Greenfield, C; General Atomics, San Diego, CA, USA; Joffrin, E; Association EURATOM-CEA, CEA/DSM/DRFC, CEA Cadarache, France; Na, Y S; Max-Planck-Institut für Plasmaphysik, EURATOM-IPP Association, Garching, Germany; Korea Basic Science Institute, 52 Yeoeun-Dong, Yusung-Gu, Daejeon, 305-333, Korea; Parail, V V; EURATOM/UKAEA Fusion Association, Culham Science Centre, UK; Sakamoto, Y; Naka Fusion Research Establishment, Japan Atomic Energy Research Institute, Naka-machi, Naka-gun, Ibaraki-ken 311-0193, Japan; Sips, A C C; Max-Planck-Institut für Plasmaphysik, EURATOM-IPP Association, Garching, Germany; Voitsekovitch, I; EURATOM/UKAEA Fusion Association, Culham Science Centre, UK; , ;
Журнал:
Plasma Physics and Controlled Fusion
Дата:
2005-12-01
Аннотация:
Current diffusion, heat transport modelling, and linear gyrokinetic stability analysis have been carried out on a set of seven hybrid discharges from AUG, DIII-D, JET and JT-60U, in order to gain better understanding of the physics underlying this promising candidate scenario for ITER. Within this dataset, the GLF23 model has a higher accuracy than the Weiland model in predicting the temperature profiles in the region 0.3 < ρ < 0.8. The core heat transport appears to be similar between hybrid discharges and standard H-modes, and also among hybrid discharges with very different H factors. Projections to ITER show that Q = 10 can be obtained with the hybrid scenario using an alternative scaling without β degradation. However, additional off-axis current drive and current profile control might be needed for the ITER hybrid scenario, in order to achieve its full potential for high β<sub>N</sub> on extended duration.
285.8Кб